ML032810039
| ML032810039 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/17/2003 |
| From: | Skay D NRC/NRR/DLPM/LPD1 |
| To: | Skolds J AmerGen Energy Co |
| Skay D, NRR/DLPM, 415-1322 | |
| References | |
| Download: ML032810039 (8) | |
Text
October 17, 2003 Mr. John L. Skolds, Chairman and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
THREE MILE ISLAND NUCLEAR STATION, UNIT 1 (TMI-1) - UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION
Dear Mr. Skolds:
Inservice inspections of steam generator (SG) tubes play a vital role in assuring that adequate structural integrity of the tubes is maintained. As required by the plant technical specifications, reporting requirements range from submitting a special report within 15 days following completion of each inservice inspection of SG tubes that identifies the number of tubes plugged and/or repaired, to submitting a special report within 12 months following completion of the inspection that provides complete results of the SG tube inservice inspection. The special report containing the complete results shall include the following:
- 1. Number and extent of tubes inspected
- 2. Location and percent of wall-thickness penetration for each indication of an imperfection
- 3. Identification of tubes plugged and/or repaired A phone conference has been arranged with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming TMI-1 refueling outage.
This phone call will occur after the majority of the tubes have been inspected, but before the SG inspection activities have been completed. Enclosed is a list of discussion points for this phone conference.
The staff plans to document a brief summary of the conference call as well as any material that you may have provided to the staff in support of the call.
Sincerely,
/RA/
Donna M. Skay, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-289
Enclosure:
List of Discussion Points cc w/encl: See next page
Three Mile Island Nuclear Station, Unit 1 cc:
Site Vice President - Three Mile Island Nuclear Station, Unit 1 AmerGen Energy Company, LLC P. O. Box 480 Middletown, PA 17057 Senior Vice President Nuclear Services AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President - Mid-Atlantic Operations Support AmerGen Energy Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA 19348 Senior Vice President -
Mid Atlantic Regional Operating Group AmerGen Energy Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA 19348 Vice President -
Licensing and Regulatory Affairs AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 Regional Administrator Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Chairman Board of County Commissioners of Dauphin County Dauphin County Courthouse Harrisburg, PA 17120 Chairman Board of Supervisors of Londonderry Township R.D. #1, Geyers Church Road Middletown, PA 17057 Senior Resident Inspector (TMI-1)
U.S. Nuclear Regulatory Commission P.O. Box 219 Middletown, PA 17057 Director - Licensing - MId-Atlantic Regional Operating Group AmerGen Energy Company, LLC Nuclear Group Headquarters Correspondence Control P.O. Box 160 Kennett Square, PA 19348 Rich Janati, Chief Division of Nuclear Safety Bureau of Radiation Protection Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Three Mile Island Nuclear Station, Unit 1 Plant Manager AmerGen Energy Company, LLC P. O. Box 480 Middletown, PA 17057 Regulatory Assurance Manager - Three Mile Island Nuclear Station, Unit 1 AmerGen Energy Company, LLC P.O. Box 480 Middletown, PA 17057 John F. Rogge, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Michael A. Schoppman Framatome ANP Suite 705 1911 North Ft. Myer Drive Rosslyn, VA 22209 Vice President, General Counsel and Secretary AmerGen Energy Company, LLC 2301 Market Street, S23-1 Philadelphia, PA 19101 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803
Three Mile Island Nuclear Station, Unit 1 cc:
Eric Epstein TMI Alert 4100 Hillsdale Road Harrisburg, PA 17112 Correspondence Control Desk AmerGen Energy Company, LLC 200 Exelon Way, KSA 1-N Kennett Square, PA 19348 Manager Licensing - Oyster Creek and Three Mile Island AmerGen Energy Company, LLC Nuclear Group Headquarters Correspondence Control P.O. Box 160 Kennett Square, PA 19348
October 17, 2003 Mr. John L. Skolds, Chairman and Chief Executive Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
THREE MILE ISLAND NUCLEAR STATION, UNIT 1 (TMI-1) - UPCOMING STEAM GENERATOR TUBE INSERVICE INSPECTION
Dear Mr. Skolds:
Inservice inspections of steam generator (SG) tubes play a vital role in assuring that adequate structural integrity of the tubes is maintained. As required by the plant technical specifications, reporting requirements range from submitting a special report within 15 days following completion of each inservice inspection of SG tubes that identifies the number of tubes plugged and/or repaired, to submitting a special report within 12 months following completion of the inspection that provides complete results of the SG tube inservice inspection. The special report containing the complete results shall include the following:
- 1. Number and extent of tubes inspected
- 2. Location and percent of wall-thickness penetration for each indication of an imperfection
- 3. Identification of tubes plugged and/or repaired A phone conference has been arranged with members of your staff to discuss the ongoing results of the SG tube inspections to be conducted during the upcoming TMI-1 refueling outage.
This phone call will occur after the majority of the tubes have been inspected, but before the SG inspection activities have been completed. Enclosed is a list of discussion points for this phone conference.
The staff plans to document a brief summary of the conference call as well as any material that you may have provided to the staff in support of the call.
Sincerely,
/RA/
Donna M. Skay, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-289
Enclosure:
List of Discussion Points cc w/encl: See next page DISTRIBUTION PUBLIC PDI-1 R/F RLaufer DSkay OGC MOBrien MMurphy CKhan BPlatchek, RGN-I ACRS ACCESSION NO.: ML032810039 OFFICE PDI-1\\PM PDI-2\\LA PDI-1\\SC NAME DSkay MOBrien RLaufer DATE 10/15/03 10/14/03 10/15/03 OFFICIAL RECORD COPY
STEAM GENERATOR (SG) TUBE INSPECTION DISCUSSION POINTS PREPARED BY THE OFFICE OF NUCLEAR REACTOR REGULATION AMERGEN ENERGY COMPANY, LLC THREE MILE ISLAND NUCLEAR STATION, UNIT 1 (TMI-1)
DOCKET NO. 50-289 The following discussion points have been prepared for the phone conference arranged with AmerGen Energy Company, LLC (the licensee), to discuss the results of the SG tube inspections to be conducted during the upcoming TMI-1 refueling outage. This phone call is scheduled to occur towards the end of the planned SG tube inspection interval, but before the unit exits its refueling outage.
The staff plans to document a brief summary of the conference call as well as any material that you may have provided to the staff in support of the call.
1.
Discuss whether any primary to secondary leakage existed in this unit prior to shutdown.
2.
Discuss the results of secondary side pressure tests.
3.
For each SG, provide a description of areas examined, including the expansion criteria utilized and type of probe used in each area. Also, be prepared to discuss your inspection of the tube within the tubesheet, particularly the portion of the tube below the expansion/transition region.
4.
Discuss any exceptions taken to the industry guidelines.
5.
Provide a summary of the number of indications identified to-date of each degradation mode and SG tube location (e.g., tube support plate, top-of-tubesheet, etc.). Also, provide information, such as voltages, and estimated depths and lengths of the most significant indications.
6.
Describe repair/plugging plans for the SG tubes that meet the repair/plugging criteria.
7.
Discuss the previous history of SG tube inspection results, including any "look backs" performed. Specifically for significant indications or indications where look backs are used in support of dispositioning (e.g., manufacturing burnish marks).
8.
Discuss, in general, new inspection findings (e.g., degradation mode or location of degradation new to this unit).
9.
Discuss your use or reliance on inspection probes (eddy current or ultrasonic) other than bobbin and typical rotating probes, if applicable.
Enclosure 10.
Describe in-situ pressure test plans and results, if applicable and available, including tube selection criteria.
11.
Describe tube pull plans and preliminary results, if applicable and available; include tube selection criteria.
12.
Discuss the assessment of tube integrity for the previous operating cycle (i.e., condition monitoring).
13.
Provide the schedule for SG-related activities during the remainder of the current outage.
14.
Discuss the following regarding loose parts:
what inspections are performed to detect loose parts a description of any loose parts detected and their location within the SG if the loose parts were removed from the SG indications of tube damage associated with the loose parts the source or nature of the loose parts if known 15.
Once-Through SGs - if you have Babcock and Wilcox (B&W) welded plugs installed in the SGs, be prepared to discuss the actions taken in response to Framatomes notification of the effect of tubesheet hole dilation on the service life of B&W welded plugs.
16.
Once-Through SGs - describe your inspection/plugging plans with respect to the industry identified severed tube issue (Nuclear Regulatory Commission Information Notice (IN) 2002-02 and IN 2002-02, Supplement 1).
17.
If SGs contain thermally treated tubing (Alloy 600 or 690), discuss actions taken, if any, based on Seabrooks recent findings (Reference IN 2002-21).